WCLL and HCCP test blanket systems: common technologies and integration in ITER

The WCLL (Water-Cooled Lead Lithium) and HCCP (Helium-Cooled Ceramic Pebbles)-TBS (Test Blanket Systems) are prototypes at small scale of the two corresponding breeding blanket concepts for DEMO and future fusion reactors. The two TBSs will be tested in ITER in the frame of the ITER TBM Program and are currently under the final part of the preliminary design phase. They will be installed in the same areas of the ITER Tokamak Complex, having then similar interfaces with different ITER systems. In the context of a close collaboration between the ITER Organization (IO) in its role of nuclear operator and the ITER Members owners of the two TBS, specific studies are ongoing on the main integration issues in the Port Cell (PC)#16. In fact, this is a critical area due to the high density of TBS components and to the severe environmental conditions (neutron and gamma irradiation, magnetic field, tritium contamination). After a recall of the main WCLL and HCCP-TBS features, the paper describes the most relevant integration issues in PC#16 together with the adopted technical solutions in the first phase of the integration studies. In addition, starting from the performed integration activities, some elements of RoX (Return on Experience) for the breeding blanket designers are also identified and discussed.

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Publication Details

Journal
Fusion Engineering and Design
Published
2026-10-16
DOI
https://doi.org/10.1016/j.fusengdes.2026.116078
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
0.00

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article

WCLL and HCCP test blanket systems: common technologies and integration in ITER

Myungho Kim, Marco Fabbri, Salvatore D’Amico, I. Ricapito et al.
Fusion Engineering and Design
Fusion materials and technologies
article

WCLL and HCCP test blanket systems: common technologies and integration in ITER

Myungho Kim, Marco Fabbri, Salvatore D’Amico, I. Ricapito, Seungyon Cho, Patrick Sauvan, Monica Martinez, Farid Tata-Ducru, J. van der Laan, E. Garcia, D. Guerra, M.Y. Ahn, R. Rosescu, B. Bellin, C. Ortiz, A. Aiello, L. Giancarli, R. Rotella, Y. Lee, F. Fantini
article en

Abstract

The WCLL (Water-Cooled Lead Lithium) and HCCP (Helium-Cooled Ceramic Pebbles)-TBS (Test Blanket Systems) are prototypes at small scale of the two corresponding breeding blanket concepts for DEMO and future fusion reactors. The two TBSs will be tested in ITER in the frame of the ITER TBM Program and are currently under the final part of the preliminary design phase. They will be installed in the same areas of the ITER Tokamak Complex, having then similar interfaces with different ITER systems. In the context of a close collaboration between the ITER Organization (IO) in its role of nuclear operator and the ITER Members owners of the two TBS, specific studies are ongoing on the main integration issues in the Port Cell (PC)#16. In fact, this is a critical area due to the high density of TBS components and to the severe environmental conditions (neutron and gamma irradiation, magnetic field, tritium contamination). After a recall of the main WCLL and HCCP-TBS features, the paper describes the most relevant integration issues in PC#16 together with the adopted technical solutions in the first phase of the integration studies. In addition, starting from the performed integration activities, some elements of RoX (Return on Experience) for the breeding blanket designers are also identified and discussed.

Fusion Engineering and DesignVol. 234
ITER (FR), Applied Materials (United Kingdom) (GB), Clínica Diagonal (ES), Institut de Recherche sur la Fusion par confinement Magnétique (FR), Fusion for Energy (ES)
Fusion for Energy
Affordable and clean energy
Openalex Percentile: Top 28%
Fusion materials and technologies
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